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See also: [[see also::IR 07100102/2012013]]


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ENGLOSURE 1 NOTICE OF VIOLATION Wolf Creek Nuclear Operating Corporation                          Docket No.:      50-482 Wolf Creek Generating Station                                    License No.:      NPF-42 Dt ring an NRC inspection conducted on November 2 through December 13,1997, two violations of NRC requirements we;e identified. In accordanrt          the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG . w, the violations are listed below:
.
A.      Technical Spee fication 6.8.1.a requires, in part, that written procedures be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
                                                  ENGLOSURE 1
Regulatory Guide 1.33, Revision 2, February 1978, Se: tion 2, recommends, in part, that procedures be established for general plant operations.
                                              NOTICE OF VIOLATION
General Operating Procedure GEN 00-008,
      Wolf Creek Nuclear Operating Corporation                          Docket No.:      50-482
* Reduced icventory Operations.' Devision 5, action 5.16.2, requires that personnel be stationed at affected containment hatches a.'' v. Jole purpose is to close the hatch prior to the onset of core boiling in the event t' at decay heat removalls lost, and that a means of communication be established ootween the contro! room and th3 stationed personnel.
      Wolf Creek Generating Station                                    License No.:      NPF-42
Contrary to the above, on November 13,1997, the inspectors noted that the containment coordinator had been assigned the duty of closing the containment hatch while retaining the balance of the containment coordinator duties, and control room personnel were not able to contact the containment coordinator when requested by the inspectors.
      Dt ring an NRC inspection conducted on November 2 through December 13,1997, two
This is a Severity Level IV violation (Supplement I) (50-482/9722 01).
      violations of NRC requirements we;e identified. In accordanrt          the " General Statement of
B.      Cnterion V of Appendix B to 10 CFR f art 50 requires, in part, that activities affecting quakty shall be prescribed by documented instructions, procedures, and drawings appropriate to the circumstances, and shall be accomplished in accordance with these instructions, procedures, or dawings.
      Policy and Procedure for NRC Enforcement Actions," NUREG . w, the violations are listed
Procedure AP 20-002,
      below:
* Post-Trip Review," Revision 0, Section 6.6.1, requires the shift supervisor or appointed senior reactor operator to ensure that the event is properly evaluated and analyzed. This review is to include a determination of whether all major safety related and other important equipment invoived in the trip operated as anticipated or expected.
      A.      Technical Spee fication 6.8.1.a requires, in part, that written procedures be established,
Contrary to the above, on November 29,1997, the appointed senior reactor operator signed the posttrip review package recommending restart, yet failed to identify the error in the initial 10 CFR 60.72 report, which was part of the posttrip data package. The initial report identified the cause of the start of both motor driven auxiliary feedwater pumps as 9901060076 971229 PDR    ADOCK 05000482 0                      PDR
              implemented, and maintained covering the applicable procedures recommended in
              Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
              Regulatory Guide 1.33, Revision 2, February 1978, Se: tion 2, recommends, in part, that
              procedures be established for general plant operations.
              General Operating Procedure GEN 00-008, * Reduced icventory Operations.' Devision 5,
                  action 5.16.2, requires that personnel be stationed at affected containment hatches
              a.'' v. Jole purpose is to close the hatch prior to the onset of core boiling in the event
              t' at decay heat removalls lost, and that a means of communication be established
              ootween the contro! room and th3 stationed personnel.
              Contrary to the above, on November 13,1997, the inspectors noted that the containment
              coordinator had been assigned the duty of closing the containment hatch while retaining
              the balance of the containment coordinator duties, and control room personnel were not
              able to contact the containment coordinator when requested by the inspectors.
              This is a Severity Level IV violation (Supplement I) (50-482/9722 01).
      B.      Cnterion V of Appendix B to 10 CFR f art 50 requires, in part, that activities affecting
              quakty shall be prescribed by documented instructions, procedures, and drawings
              appropriate to the circumstances, and shall be accomplished in accordance with these
              instructions, procedures, or dawings.
              Procedure AP 20-002, * Post-Trip Review," Revision 0, Section 6.6.1, requires the shift
              supervisor or appointed senior reactor operator to ensure that the event is properly
              evaluated and analyzed. This review is to include a determination of whether all major
              safety related and other important equipment invoived in the trip operated as anticipated
              or expected.
              Contrary to the above, on November 29,1997, the appointed senior reactor operator
              signed the posttrip review package recommending restart, yet failed to identify the error
              in the initial 10 CFR 60.72 report, which was part of the posttrip data package. The initial
              report identified the cause of the start of both motor driven auxiliary feedwater pumps as
  9901060076 971229
  PDR    ADOCK 05000482
  0                      PDR
                                                                            ,


9 2                                                ,
9
a low steam generator level below 23.5 percent, yet the steam generator levels did not approach or decline below the low level cetpoint.
                                                    2                                                ,
This is i Severity Level IV violation (Supplement 1) (50-482/9722-02).
          a low steam generator level below 23.5 percent, yet the steam generator levels did not
Pursuant to the provisions of 10 CFR 2.201, Wolf Creek Nuclear Operating Corporation is hereby requi"sd to submit a written statement or exclaqation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555, with a copy to the Regional Administrator, Region IV,611 Ryan Plaza Drive, Suite 400, Arlington. Texas 76011, and a copy to the NRC Resident Irispectors at the facility that is the subject oM s Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This rep!y should be clearly marked as a " Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation, c' # contested, the bash for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance w;il be achieved. Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response, if an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
          approach or decline below the low level cetpoint.
Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the POR without redaction. However, if you find it necessary to include such information, you should clearly indicato the specific information that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information from the public.
          This is i Severity Level IV violation (Supplement 1) (50-482/9722-02).
Dated at Arlington, Texas this 29 day of December,1997 l
  Pursuant to the provisions of 10 CFR 2.201, Wolf Creek Nuclear Operating Corporation is
l l
  hereby requi"sd to submit a written statement or exclaqation to the U.S. Nuclear Regulatory
                                                                                                       '}}
  Commission, ATTN: Document Control Desk, Washington, D.C. 20555, with a copy to the
  Regional Administrator, Region IV,611 Ryan Plaza Drive, Suite 400, Arlington. Texas 76011,
  and a copy to the NRC Resident Irispectors at the facility that is the subject oM s Notice, within
  30 days of the date of the letter transmitting this Notice of Violation (Notice). This rep!y should
  be clearly marked as a " Reply to a Notice of Violation" and should include for each violation: (1)
  the reason for the violation, c' # contested, the bash for disputing the violation, (2) the
  corrective steps that have been taken and the results achieved, (3) the corrective steps that will
  be taken to avoid further violations, and (4) the date when full compliance w;il be achieved. Your
  response may reference or include previous docketed correspondence, if the correspondence
  adequately addresses the required response, if an adequate reply is not received within the
  time specified in this Notice, an order or a Demand for Information may be issued as to why the
  license should not be modified, suspended, or revoked, or why such other action as may be
  proper should not be taken. Where good cause is shown, consideration will be given to
  extending the response time.
  Because your response will be placed in the NRC Public Document Room (PDR), to the extent
  possible, it should not include any personal privacy, proprietary, or safeguards information so
  that it can be placed in the POR without redaction. However, if you find it necessary to include
  such information, you should clearly indicato the specific information that you desire not to be
  placed in the PDR, and provide the legal basis to support your request for withholding the
  information from the public.
  Dated at Arlington, Texas
  this 29 day of December,1997
                                                                                                      l
                                                                                                      l
                                                                                                      l
                                                                                                       '
}}

Latest revision as of 13:47, 8 September 2023

Notice of Violation from Insp on 971102-1213.Violations Noted:On 971113,inspectors Noted That Containment Coordinator Had Been Assigned Duty of Closing Containment Hatch While Retaining Balance of Coordinator Duties
ML20198A751
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 12/29/1997
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20198A725 List:
References
50-482-97-22, NUDOCS 9801060076
Download: ML20198A751 (2)
v • d • e


See also: IR 07100102/2012013

Text

,

.

ENGLOSURE 1

NOTICE OF VIOLATION

Wolf Creek Nuclear Operating Corporation Docket No.: 50-482

Wolf Creek Generating Station License No.: NPF-42

Dt ring an NRC inspection conducted on November 2 through December 13,1997, two

violations of NRC requirements we;e identified. In accordanrt the " General Statement of

Policy and Procedure for NRC Enforcement Actions," NUREG . w, the violations are listed

below:

A. Technical Spee fication 6.8.1.a requires, in part, that written procedures be established,

implemented, and maintained covering the applicable procedures recommended in

Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

Regulatory Guide 1.33, Revision 2, February 1978, Se: tion 2, recommends, in part, that

procedures be established for general plant operations.

General Operating Procedure GEN 00-008, * Reduced icventory Operations.' Devision 5,

action 5.16.2, requires that personnel be stationed at affected containment hatches

a. v. Jole purpose is to close the hatch prior to the onset of core boiling in the event

t' at decay heat removalls lost, and that a means of communication be established

ootween the contro! room and th3 stationed personnel.

Contrary to the above, on November 13,1997, the inspectors noted that the containment

coordinator had been assigned the duty of closing the containment hatch while retaining

the balance of the containment coordinator duties, and control room personnel were not

able to contact the containment coordinator when requested by the inspectors.

This is a Severity Level IV violation (Supplement I) (50-482/9722 01).

B. Cnterion V of Appendix B to 10 CFR f art 50 requires, in part, that activities affecting

quakty shall be prescribed by documented instructions, procedures, and drawings

appropriate to the circumstances, and shall be accomplished in accordance with these

instructions, procedures, or dawings.

Procedure AP 20-002, * Post-Trip Review," Revision 0, Section 6.6.1, requires the shift

supervisor or appointed senior reactor operator to ensure that the event is properly

evaluated and analyzed. This review is to include a determination of whether all major

safety related and other important equipment invoived in the trip operated as anticipated

or expected.

Contrary to the above, on November 29,1997, the appointed senior reactor operator

signed the posttrip review package recommending restart, yet failed to identify the error

in the initial 10 CFR 60.72 report, which was part of the posttrip data package. The initial

report identified the cause of the start of both motor driven auxiliary feedwater pumps as

9901060076 971229

PDR ADOCK 05000482

0 PDR

,

9

2 ,

a low steam generator level below 23.5 percent, yet the steam generator levels did not

approach or decline below the low level cetpoint.

This is i Severity Level IV violation (Supplement 1) (50-482/9722-02).

Pursuant to the provisions of 10 CFR 2.201, Wolf Creek Nuclear Operating Corporation is

hereby requi"sd to submit a written statement or exclaqation to the U.S. Nuclear Regulatory

Commission, ATTN: Document Control Desk, Washington, D.C. 20555, with a copy to the

Regional Administrator, Region IV,611 Ryan Plaza Drive, Suite 400, Arlington. Texas 76011,

and a copy to the NRC Resident Irispectors at the facility that is the subject oM s Notice, within

30 days of the date of the letter transmitting this Notice of Violation (Notice). This rep!y should

be clearly marked as a " Reply to a Notice of Violation" and should include for each violation: (1)

the reason for the violation, c' # contested, the bash for disputing the violation, (2) the

corrective steps that have been taken and the results achieved, (3) the corrective steps that will

be taken to avoid further violations, and (4) the date when full compliance w;il be achieved. Your

response may reference or include previous docketed correspondence, if the correspondence

adequately addresses the required response, if an adequate reply is not received within the

time specified in this Notice, an order or a Demand for Information may be issued as to why the

license should not be modified, suspended, or revoked, or why such other action as may be

proper should not be taken. Where good cause is shown, consideration will be given to

extending the response time.

Because your response will be placed in the NRC Public Document Room (PDR), to the extent

possible, it should not include any personal privacy, proprietary, or safeguards information so

that it can be placed in the POR without redaction. However, if you find it necessary to include

such information, you should clearly indicato the specific information that you desire not to be

placed in the PDR, and provide the legal basis to support your request for withholding the

information from the public.

Dated at Arlington, Texas

this 29 day of December,1997

l

l

l

'

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